ML17252A246

Letter Submitting Reportable Occurrence Number 050-249/1976-23 in Accordance with Technical Specifications, Section 6.6.B

ML17252A246
Person / Time
Site:	Dresden
Issue date:	11/04/1976
From:	Stephenson B Commonwealth Edison Co
To:	James Keppler NRC/RGN-III
References
BBS Ltr. #76-775
Download: ML17252A246 (3)

Text

.**. Comrnonv.h Edison

• Dresde,1 Nuclear Power Station R.R. #i Morris, Illinois 60450 Telephone 815/942-2920 BBS Ltr. #76-775 November 4, 1976 Mr. James G~ Keppler, Regional Director Directorate of R~gulatory Operations -.Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 Enclosed please find Reportable Occurrence report number 50-249/1976-23.

This report is being submitted to your office in accordance with the Dresden Nuclear Powe~ Station Techriical ~pecifications, Section 6.6.B.

A n n. :. *1Y) _/) ~.. * -I-h un~.. ~

. B. Stephensori

• tation Superintendent.

Dresden Nuclear Power Station BBS :jo Enclosure cc:

Director of Inspection & *Enforcement

. Direct'or of Management Information & Program Control File/NRC

~*

LICENSEE EVd\\JT REPOR.

' CONTROL BLOCK: I '

I *.1

1. I I (PLEASE PRll'JT ALL REQUIRED INFORMATION) 1 6

LICENSEE NAME

.@El I I I L. ID IR I s 13 I 7

8 9

' 14 CATEGORY REPORT TYPE.

LICENSE NUMBER 10101-10101010101-10101 15 25 REPORT SOURCE OOCl\\ET NUM6ER

• LICENSE TYPE 1!1111111111 26

' 30 EVENT TYPE 10131

'31

' 32' EVENT* DATE REPORT DATE lof1 I coN1 I I I 7

8 57 58' llJ 59 LLl 60 101s101~101~1~191 61 68 11 IOIOl?l71(,l.*II II 1014171(, L 69 74 75 80 EVENT DESCRIPTION.

(filg].lD!JRtAJ.G-REFUELING-OUTAGE LDC.AL l.t:Ak-:-RATE TESTING; *LPC/ PRtrnARV I 7*

8' 9

80.

lol31 ltSO.L..ATION'.

CA*IE:CI<

VfU;V 3-!S-O/-J.5& £XHtBtT£.D A l...EAr<AC-£ RAT£.... U!J' I, 7

Ei' 9 80

~

IEXC£$$'0F /HT:; T£CH SP£.C. /_JM/{ OF.J.Cf.~f!/_. SC'l="H. TH OTH~g*. VAL.VE:

I 7

8 9 '

80 10'51 lusED VO f6R<YYI THE. 4'?'-Psf(:; PRESSUfV~ DECAY 7EST BouJVDl1R..Y.. fYlANuALf 7

8 9 i

80 lolsl I VAt..VE'.' 3-15°0! -:Y,,B J 1-lfJD A $ IGNI FICA NT WATER HC/IJ) PR£s£NTj CONSEQLJOJT1..y,, I 7

8 9.

PRIME (5,£ /IT!FICHEV -<;;ft£GT) 80 SYSTEM CAUSE COMPONENT COMPON!:NT

. CODE CODE

• COMPONENT CODE SUPPLIER MANUFACTURER VIOLATION

@0 ISIFLlsJ 1v1AIL1v1£1x1 lt!J 1A1s1*~1s1 L'Ll 7

8 9 10

' 11 12 17

' 43 44 4 7 48

. CAUSE DES.CA!PTION

~

l::TJ1£ VA/..-1/E f:fll L-UR.6

'WA~ CAUSED Bi EXCESS I 116 ])15C-To -SEAi 1-£AKAG-~.

J 7

8 9 80 lo'91 l1r1cs J.£AK-fK-G:

i,.JA~ A77R.t8UIED,.. To TH£ PREsEl'JCG.* OE DtRTA*No

• SIYIAL-t~

I 7

8 9

' 80. '

,.~.: (iE1.I S:CRATc.HC:S OtJ THE Vf/LV~ $£fl'0 APPARENTLY IHE REs()t,..T oF.Jv'ORWl,fiL.W£AR. J

' 7 ;*, 8 9,: FACILllY METHOD OF

' 'Js:t:E-:/rrjA~/t;F,.P ~}:/.!)

. co

' STATUS

• %.. POWER OTHER STATUS OISCOVEAY

• DISCOVERY DESC.RIPTION EE], lHJ

• l O 16 l 61 *1..__"'""-'.AJ'--A _

___,I. lBJ

,__,,..-.N-.;,..11'-'--. ---~..,.-.-'-._-_

. 7. ** 0**

9*

• .10 *

• 12 13 44 **

45

• • . 46 so FORM OF ACTIVITY CONTENT

• RELEASED OF RELEASE AMOUNT OF ACTIVITY rn. lZJ

• l~J *I.__* --~N_ll __

I LOCATION OF RELEASE 7

8 9

10 11 44 45 '

80 PERSONNEL EXPOSURES NUMBER

• TYPE DESCRIPTION

~ lo Io JO I : ~. ~-.....::.JtJ_tt~--,---.,.---------~-------~-~-"-'-'-'-:-'-'------__.___,

7 * *a s 11

• 12..

13 ea.

PERS'ONNEL INJURIES NUMBER.

OESCRIPTION v.

[EJ*1n10.l.ol L--..;.

.. _**-* _A_f1_. _* --------------------J 7

8 ~

11 12 80 OFFSITE CONSEQUENCES

.Elfil I A/A 7

8 9 80

. LOSS ~F;l DAMAGE. TO FACILITY TYPE

.DESCRIPTION *

~

.~

A)ff' 7

8 9 10 80 PUBLICITY l:illl 7

8 81..;_---L.~L-----------------,-------------'-----.,---~--'-----"------.---::-2~J ADDITIONAL FACTOfiS (1JUJ

/v*>0' 7 89 80 EEi 7

89 BC NAME: __

R;._A_/i_V_])_o_'-_* *_?_1:...... 1 _c_.* _w_c._:-_r_D_M_'E----'R"-. ---~

PHONE: £xT. d...G 5

~..

EVENT DESCRIPTION (Continued) the as-found leakage of 61.0 SCFH was attributed entirely to leakage through check valve 1501-25B.

A second leak test using valves 1501-26B, i501-22B, and 1001-SB as boundaries yielded a leakage rate of 4.2 SCFH:

Since.the second test volume included the volume of the previous test, total through-leakage for the penetration was well under the Tech Spec limit.

A similar valve on Unit-2 failed 16cal leak~rate testing in early 1975.

(50-249/1976-23)

CAUSE DESCRIPTION. (Continued)

The valve was disassembled, the seat was lapped, and the packing and _Flexitallic gasket were replaced.

Leak-rate testing of the reassembled valve was satisfactory.

In 1975, a test/drain line was installed on this penetration which permitted leak-rate testing of check valve 3-1501-25B for the first time since unit oper-ation began.

Since this valve has performed* satisfactorily over a period of several years, testing of this vaLve on an approximately annual basis should permit timely identification of a recurring problem.

• Valve 3-15.0l-25B is a 16-inch tilting disc check valve, manufactured by.Atwood and Morrill Company, Inc.